In the four-stage approach of the new ITER Research Plan, the first Pre-Fusion Power Operation (PFPO) phase will only have a limited power available from external Heating and Current Drive (H&CD) systems: 20 to 30 MW, provided by the Electron Cyclotron Resonance Heating system (ECRH). Accessing the H-mode confinement regime at such low auxiliary power requires operating at lower magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. H-mode plasmas at 5 MA / 1.8 T are also considered for the second PFPO phase when ITER will have its full installed H&CD capabilities, i.e. 20−30 MW of ECRH, 20 MW of Ion Cyclotron Resonance Heating (ICRH) and 33 MW of Neutral Beam Injection (NBI). The present paper describes the operational conditions of such scenarios in hydrogen and helium plasmas and the H&CD capabilities for these plasmas, to assess the viability of such scenarios and the issues that will be possible to address with them. The modelling results show that 5 MA / 1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.